Thanks to visit codestin.com
Credit goes to github.com

Skip to content
View dragon-hee's full-sized avatar

Block or report dragon-hee

Block user

Prevent this user from interacting with your repositories and sending you notifications. Learn more about blocking users.

You must be logged in to block users.

Maximum 250 characters. Please don't include any personal information such as legal names or email addresses. Markdown supported. This note will be visible to only you.
Report abuse

Contact GitHub support about this user’s behavior. Learn more about reporting abuse.

Report abuse
Showing results

Fortran code demonstrating the Method of Long Characteristics neutronics model on a 3x3 lattice of UO2 and MOX fuel pins

Fortran 1 Updated Oct 26, 2018

Neutron transport with the method of characteristics

Julia 1 1 Updated Nov 17, 2022

Uses Method of Characteristics to solve 2D box problem with a central inner isometric box source

MATLAB 1 1 Updated Nov 22, 2020

Method of Characteristics neutron transport solver on OpenFOAM. Very old, slightly embarrassing.

C 5 4 Updated Nov 23, 2016

High performance cyclic ray tracing algorithm for neutron transport in Julia.

Julia 17 1 Updated Jul 28, 2025

Solves the RTE using the MOC on tetraedral meshes

C++ 3 1 Updated Mar 11, 2025

NRE 6103 Project - Collision Probability Method

C++ 1 1 Updated Apr 11, 2025

clone of diamond difference method configured to run with response matrix method for extended domains

Fortran 1 Updated Aug 25, 2017

Open Nuclear Reactor Simulator

Fortran 65 15 Updated Apr 25, 2025

An open source nodal solver for nuclear reactors.

Fortran 4 1 Updated Sep 10, 2022

SKETCH-N is a nodal code for solving neutron diffusion equations of steady-state and kinetics problems

Fortran 1 Updated Aug 7, 2025

Software package for nodal quasi-diffusion solvers for neutronic analysis.

Python 1 1 Updated May 30, 2018

Solves the multigroup Neutron Diffusion equation using the Nodal methods in 3D Cartesian geometries

Python 2 2 Updated Oct 4, 2024

An Open Nuclear Reactor Simulator and Reactor Core Analysis Tool

Fortran 27 10 Updated Jan 9, 2021

A discrete ordinates (Sn) neutron transport code for pin cell spectral calculations

Python 3 1 Updated Oct 29, 2017

Neutron transport solver using collision probability method

C++ 4 2 Updated Apr 8, 2025

1D Sn Neutron Transport Solver

C++ 4 1 Updated Dec 7, 2019

A Discrete Ordinates (SN) Multigroup Neutron Transport Code.

Cython 3 2 Updated Oct 16, 2025

Two-dimensional discrete ordinates neutron transport equation solver for NE155 - Introduction to Numerical Simulations in Radiation Transport at UC Berkeley

C++ 9 2 Updated Dec 13, 2016

A neutron transport equation eigenvalue solver based on Discrete Ordinates Method.

Fortran 9 4 Updated Sep 8, 2025

Three-Dimensional Discrete Ordinates Neutron, Photon, Electron and Positron Transport Code

ReScript 10 4 Updated Feb 26, 2022

Sn neutron transport written mostly in python. For university Sn transport theory class.

Python 12 6 Updated Aug 23, 2017

Method of Characteristics neutral particle transport code for reactor physics written in Julia.

Julia 27 3 Updated Jul 10, 2023

Helios - A C++ Monte Carlo Neutron Transport Code

C++ 20 11 Updated Jun 27, 2020

Test code for 2D transient neutron diffusion equation based on the finite difference method (FDM) and stiffness confinement method (SCM).

Jupyter Notebook 5 3 Updated Jul 29, 2021

Class Project Simple finite-volume based neutron diffusion solver using MOOSE

C++ 8 9 Updated Jul 20, 2023

Finite Volume Neutron Diffusion solver for Oli

Fortran 1 Updated Dec 6, 2023

A neutron transport code based on the finite volume method.

C++ 2 1 Updated Jun 13, 2025

This project focuses on the evaluation of 4 different numerical schemes / methods based on the Finite Difference (FD) approach in order to compute the solution of the 1D Heat Conduction Equation wi…

C++ 9 1 Updated Aug 12, 2021

CUDA Library Samples

Cuda 2,139 415 Updated Oct 20, 2025
Next